ML17264B122
| ML17264B122 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/28/1997 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17264B123 | List: |
| References | |
| TAC-M96529, NUDOCS 9712030207 | |
| Download: ML17264B122 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&(I001 November 28, 1997 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
R.
E.
GINNA ACCEPTANCE FOR REFERENCING OF PRESSURE TEMPERATURE LIMITS REPORT, REVISION 2 (TAC NO. H96529)
Dear Dr. Hecredy:
REFERENCES:
1.
2.
3.
4.
5.
Amendment No.
48 to Facility Operating License No. DPR-18, R.
E. Ginna Nuclear Power Plant, March 6, 1992.
Letter from C. I. Grimes, NRC, To R. A. Newton, Westinghouse Electric Corporation, "Acceptance for Referencing of Topical Report WCAP-14040, Revision 1,
'Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves,'" October 16, 1995.
(Also known as WCAP-14040-NP-A).
Letter from R.
C. Mecredy, Rochester Gas and Electric Corporation (RG&E), to Document Control Desk, NRC, Attention A. R. Johnson, "Application for Amendment to Facility Operating License Methodology for Low Temperature Overpressure Protection (LTOP) Limits," February 9, 1996.
Letter from A. R. Johnson, NRC, to R.
C. Hecredy, Rochester Gas and Electric Corporation (RG&E), "R.
E. Ginna Nuclear Power Plant Pressurized Thermal Shock Evaluation (TAC No.
M93827)," March 22, 1996.
Letter from R.
C. Hecredy, Rochester Gas and Electric Corporation (RG&E), to Document Control Desk, NRC, Attention A. R. Johnson, "Application for Amendment to Facility Operating License Revision to Reactor Coolant System (RCS)
Pressure and Temperature Limits Report (PTLR)," April 22, 1996.
IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII Contacts:
Haggalean W. Weston, (301) 415-3151 Guy Vissing, (301) 415-1441 9712030207 POR AQQC P
0SOOaaee i
POP
gl P.Q jJ
Robert C. Mecredy 6.
Letter from J.
A. Mitchell, NRC, to R.
C. Hecredy, Rochester Gas and Electric Corporation, "R.
E. Ginna-Acceptance for Referencing of Pressure Temperature Limits Report, Revision 1
(TAC No. H94770),"
May 23, 1996.
7.
8.
9.
10.
12.
Amendment No. 64 to Facility Operating License No.
DPR-18, R.
E. Ginna Nuclear Power Plant, Hay 23, 1996.
Letter from R.
C. Hecredy, Rochester Gas and Electric Corporation to G. S. Vissing, NRC, "Application for Amendment to Facility Operating
- License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR), Rochester Gas and Electric Corporation, R.
E. Ginna Nuclear Power Plant, Docket No. 50-244," September 13, 1996.
(WCAP-14684 Attached).
Letter from G.
S. Vissing, NRC, to R.
C. Hecredy, Rochester Gas and Electric Corporation, "R. E. Ginna-Acceptance of Request to Extend Time for Approval of Revision of Pressure and Temperature Limits Report (PTLR)
(TAC No. M97313)," December 10, 1996.
Letter from R.
C. Hecredy, Rochester Gas and Electric Corporation to G. S. Vissing, NRC, "Application for Amendment to Facility Operating License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) Administrative Controls Requirements, Rochester Gas and Electric Corporation, R.
E. Ginna Nuclear Power Plant, Docket No. 50-244,"
April 24, 1997.
Letter from R.
C. Hecredy, Rochester Gas and Electric Corporation to G.
S. Vissing, NRC, "Clarifications to Proposed Low Temperature Overpressure Protection (LTOP) Technical Specification, Rochester Gas and Electric Corporation, R.
E. Ginna Nuclear Power Plant, Docket No. 50-244," June 3, 1997.
Letter from R.
C. Hecredy, Rochester Gas and Electric Corporation,'Request for Exemption from 10 CFR 50.60, Acceptance Criteria for Fracture Prevention for Light Water Nuclear Power Reactors for Normal Operation,."
June 12, 1997.
Robert C. Hecredy 13.
14.
Letter from G. S. Vissing, NRC to R.
C. Hecredy, Rochester Gas and Electric Corporation, "R. E. Ginna-Acceptance of Request to Extend Time for Approval of Revision of Pressure and Temperature Limits Report (PTLR)
(TAC No. H98992)," June 26, 1997.
Letter from G. S. Vissing, NRC to R.
C. Hecredy, Rochester Gas and Electric Corporation, "Exemption from the Requirements of 10 CFR Part 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation
- R.
E. Ginna Nuclear Power Plant (TAC No. H98993),"
July 28, 1997.
15.
Letter from R.
C. Hecredy, Rochester Gas and Electric Corporation to G. S. Vissing, NRC, "Application for Amendment to Facility Operating
- License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) Administrative Controls Requirements, Rochester Gas and Electric Corporation, R.
E. Ginna Nuclear Power Plant, Docket No. 50-244,"
September 29, 1997.
16.
Letter from R.
C. Hecredy, Rochester Gas and Electric Corporation to G.
S. Vissing, NRC, "Corrections to Proposed Low Temperature Overpressure Protection Technical Specifications, Rochester Gas and Electric Corporation, R.
E. Ginna Nuclear Power Plant, Docket No. 50-244," October 8, 1997.
We have completed our review of the pressure temperature (P/T) and low overpressure protection (LTOP) system limits methodology and the pressure temperature limits report (PTLR) (as referenced above),
submitted by the Rochester Gas and Electric Corporation.
We find the methodology to be acceptable for referencing in the administrative controls section of the R.
E.
Ginna Nuclear Power Plant Technical Specifications (TS) to the extent specified and under the limitations del"ineated in your submittals and the associated NRC safety evaluation, which is enclosed.
The safety evaluation defines the basis for acceptance of the submittals.
Our acceptance only applies to the matters described in the submittals.
The methodology for review relating to. the P/T and LTOP system limits was provided in the references listed above.
Refer ence 3 included WCAP-14040, Revision 1
(WCAP-14040-NP-A), which provided parts of the methodology used for determining the acceptance of the R.
E. Ginna methodology.
Robert C. Hecredy The methodology in WCAP-14040, along with supplements provided by RGEE will be used to calculate future changes to the P/T and LTOP limits.
RGKE may generate new P/T and LTOP system limits in accordance with this methodology without prior approval of the staff.
System limits may be subject to audit by the staff through inspections as necessary.
Me do not intend to repeat our review of the matters described in the submittals if the submittals appear as references in other license applications relating to your plant, except to ensure that the material in the submittals is still applicable to your plant as indicated in the conclusion section of the safety evaluation.
Should our criteria or regulations change so that our conclusions as to the acceptability of the methodology is invalidated, licensees referencing these documents will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the documents without revision of their respective documentation.
Sincerely, S.
Singh Bajwa, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation cc w/encl:
See next page
1
0 I
'ovember 28, 1997
,'l Robert C. Necredy j II I
(1.'he methodology in WCAP-14040, along with supplements provided by RG&E will be used to calculate future changes to the P/T and LTOP limits.
RGSE may generate new P/T and LTOP system limits in accordance with this methodology without prior approval of the staff.
System limits may be subject to audit by the staff through inspections as necessary.
f We do not intend to repeat our review of the matters described in the submittals if the submittals appear as references in other license applications relating to your plant, except to ensure that the material in the submittals is still applicable to your plant as indicated in the conclusion section of the safety evaluation.
Should our criteria or regulations change so that our conclusions as to the acceptability of the methodology is invalidated, licensees referencing these documents will be expected 'to revise and resubmit their respective
'ocumentation, or submit justification for the continued effective applicability of the documents without revision of their respective documentation.
Docket No. 50-244
Enclosure:
Safety Evaluation cc w/encl:
See next page Sincerely, Original Signed by:
S.
Singh Bajwa, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Distribution:
Docket File BSheron WBeckner Ginna R/F GNHolahan TCollins RPZimmerman BBoger EWeiss HNiller JStrosnider SBajwa
",DOCUMENT NAME: G:>MWWIGINNAREV.LTR To receive a copy of this document, IndIcate In the born "C' Copy w/o KWichman KKarwoski PUBLIC LLois BElliot TSB R/F NShuaibi GSVissing OGC LDoerflein NWWeston ACRS THarris "See Previous Concurrence y
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Dr. Robert C. Hecredy R.E.
Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Senior Resident Inspector R.E.
Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road
- Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Hr. F. William Valentino, President New York State
- Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension
- Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S.
Reynolds Winston 5 Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 Hs. Thelma Wideman
- Director, Wayne County Emergency Hanagement Office Wayne County Emergency Operations Center 7336 Route 31
- Lyons, NY 14489 Hs. Hary Louise Heisenzahl Administrator, Honroe County Office of Emergency Preparedness ill West Fall
- Road, Room 11 Rochester, NY 14620 Hr. Paul Eddy New York State Department of Public Service 3 Empire State
- Plaza, Tenth Floor
- Albany, NY 12223